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The Code O-SUKI-N 3D is an upgraded version of the 2D Code O-SUKI (Comput. Phys. Commun. 240, 83 (2019)). Code O-SUKI-N 3D is an integrated 3-dimensional (3D) simulation program system for fuel implosion, ignition and burning of a direct-drive nuclear-fusion pellet in heavy ion beam (HIB) inertial confinement fusion (HIF).The Code O-SUKI-N 3D consists of the three programs of Lagrangian fluid implosion program, data conversion program, and Euler fluid implosion, ignition and burning program. The Code O-SUKI-N 3D can also couple with the HIB illumination and energy deposition program of OK3 (Comput. Phys. Commun. 181, 1332 (2010)). The spherical target implosion 3D behavior is computed by the 3D Lagrangian fluid code until the time just before the void closure of the fuel implosion. After that, all the data by the Lagrangian implosion code are converted to the data for the 3D Eulerian code. In the 3D Euler code, the DT fuel compression at the stagnation, ignition and burning are computed. The Code O-SUKI-N 3D simulation system provides a capability to compute and to study the HIF target implosion dynamics., Comment: 51 pages, 21 figures. Computer code is also available with an example output directory structure. arXiv admin note: substantial text overlap with arXiv:1812.07128

An ion beam has a unique feature to deposit its main energy inside a human body to kill cancer cells or inside material. In this paper, a future intense laser ion accelerator is discussed to make the laser-based ion accelerator compact and controllable. The issues in the laser ion accelerator include the energy efficiency from the laser to the ions, the ion beam collimation, the ion energy spectrum control, the ion beam bunching, and the ion particle energy control. The energy efficiency from the laser to ions is improved by using a solid target with a fine sub-wavelength structure. The ion beam collimation is performed by larger holes behind the solid target. An ion beam bunching and a post-acceleration are successfully realized by a multi-stage laser-target interaction. The controllable laser ion acceleration would become viable based on the study discussed in this paper. In this paper, we present 3D PIC simulation results for the controllability of laser ion acceleration system.

A dynamic smoothing method was proposed based on a phase control to stabilize plasma instabilities and smooth plasma non-uniformities. In this paper, the dynamic smoothing method is applied to a spherical fuel target implosion in heavy ion inertial fusion (HIF). We found that the wobbling motion of each heavy ion beam (HIB) axis induces a phase-controlled HIBs energy deposition, and consequently the phase-controlled implosion acceleration is realized, so that the HIBs illumination non-uniformity is successfully smoothed. HIB accelerators provide a well-established capability to oscillate the HIBs axes with a high frequency. In inertial confinement fusion, a fuel implosion uniformity is essentially important to compress the DT fuel and release the fusion energy, and the non-uniformity of the implosion acceleration should be less than a few %. The results in this paper also demonstrate that the wobbling HIBs would provide an improvement in the fusion energy output gain.

In inertial confinement fusion (ICF), the DT fuel should be compressed uniformly, and the ion temperature of the compressed DT should reach ~5–10 [KeV]. In order to compress the DT fuel stably to the high density, the implosion non-uniformity should be less than a few percent. In this paper, we present a fuel pellet implosion simulation system O-SUKI code in heavy ion inertial confinement fusion and its application results to parameter studies especially in the driver input pulse. It was found that the rise time period of the main pulse has a significant impact on the fuel implosion performance. We also found that an irradiation timing error of each driver beam induces an enhancement of the implosion non-uniformity, and consequently the driver beam irradiation timing error degrades the fusion energy gain.

A few percent wobbling-beam illumination nonuniformity is realized in heavy ion inertial confinement fusion (HIF) by a spiraling beam axis motion in the paper. The wobbling heavy ion beam (HIB) illumination was proposed to realize a uniform implosion in HIF. However, the initial imprint of the wobbling HIBs was a serious problem and introduces a large unacceptable energy deposition nonuniformity. In wobbling the HIBs illumination, the illumination nonuniformity oscillates in time and space. The oscillating-HIB energy deposition may contribute to the reduction of the HIBs' illumination nonuniformity and also the mitigation of the Rayleigh–Taylor instability. The wobbling HIBs can be generated in HIB accelerators and the oscillating frequency may be from several 100 MHz to 1 GHz. Three-dimensional HIBs illumination computations presented here show that the few percent wobbling HIBs illumination nonuniformity oscillates successfully with the same wobbling HIBs frequency.

Considering an inhomogeneous plasma that has trapped electrons and dust grains, we investigate the possible modes, their evolution as solitons and the reflection of solitons from the density gradient. The usual form of the Korteweg–de Vries (KdV) equation, which governs the behaviour of solitons, is modified for the present plasma, and is solved by finding appropriate transformations. The role of the charge Z d (positive: α = + 1 or negative: α = − 1 ) of the dust and dust concentration n d 0 in the presence of trapped electrons (density n e l 0 and temperature T e l 0 ) is investigated for the soliton reflection. The mode that evolves as a soliton can propagate in the plasma only when ion temperature T i ≥ α n d 0 Z d / ( n e h 0 T e h + n e l 0 T e l ) , where n e h 0 and T e h 0 are the density and temperature of nonisothermal electrons. Only the compressive solitons are found to propagate and reflect in the plasma (along with a shift) when the dust charge density remains smaller than the total charge density of the electrons of both types.

Recent research activities in Japan relevant to heavy ion fusion (HIF) are presented. During the past two years, significant progress in HIF and high energy density (HED) physics research has been made by a number of research groups in universities and accelerator facilities. Evolutions in phase space during the longitudinal compression of intense beams were investigated at UU–NUT–TIT. Beam–plasma interaction experiments and related theoretical studies are in progress at RLNR-TIT. In the study, shock-heated hydrogen was used for the interaction experiments as a well-defined non-ideal-plasma target. In the beam–plasma interaction experiments, a special emphasis is placed on an evaluation of non-linear effects on the stopping power in a beam-heated plasma target. A direct–indirect hybrid scheme of a beam-driven ICF target has been proposed and discussed at UU. In the same group, a method for controlling the Rayleigh–Taylor instability in imploding fuel target has been proposed using oscillating heavy ion beams (HIBs). Core dynamics of the impact ignition has been investigated both experimentally and numerically at ILE—Osaka. Dense plasmas driven by intense ion beams and/or a pulse powered device, were evaluated by a group of DES-TIT, concerning the researches on HED and warm dense matter (WDM) physics. A quasi-statically tamped target was proposed to make a well-defined, warm dense state for equation-of-state (EOS) studies based on ion accelerators. The potentiality of the new facility planned at KEK was evaluated by a collaborating group of TIT–UU–KEK, which can extend the parameter regime for laboratory experiments to study the properties of matter under extreme conditions. A possible method to make a high-pressure condition for study of the planetary science was discussed as a short-term subject of intense HIBs.

Uniformity of heavy ion beam (HIB) illumination is one of the key issues in HIB inertial confinement fusion (HIF): deviation from fuel implosion symmetry should be less than a few percent in order to compress a fuel sufficiently and release fusion energy effectively. In this paper, a new mitigation method of the Rayleigh–Taylor (R-T) instability growth is presented in order to make a HIF target robust against a non-uniform implosion. In this study a new mitigation method of R-T instability growth is proposed based on an oscillating perturbed acceleration, which can be realized by a rotating or oscillating HIB illumination onto a fuel pellet. The R-T instability analyses and fluid simulations demonstrate that the oscillating acceleration reduces the R-T instability growth significantly. In this paper a baseline steady acceleration g 0 is perturbed by a perturbed oscillating acceleration δg , which is spatially non-uniform and oscillates in time ( g 0 ⪢ δg ). An example result shows 84% reduction of the R-T instability growth.

The key issues in heavy ion beam (HIB) inertial confinement fusion (ICF) include particle accelerator, physics of intense beam, beam final transport, target-plasma hydrodynamics, etc. In this paper, we focus on fuel implosion. In order to realize an effective implosion, beam illumination non-uniformity on a fuel target must be suppressed less than a few percent. In this study a direct–indirect hybrid implosion mode is discussed in heavy ion beam inertial confinement fusion (HIF) in order to release sufficient fusion energy in a robust manner. In the direct–indirect hybrid mode target, a low-density foam layer is inserted, and the radiation energy is confined in the foam layer. In the foam layer, the radiation transport is expected to smoothen the HIB illumination non-uniformity in the lateral direction. In this paper, we study the influences of the foam thickness and the inner radiation-shield Al density on implosion uniformity. Two-dimensional fluid simulations demonstrate that the hybrid target contributes to the HIB non-uniformity smoothing and releases a sufficient fusion energy output in HIF.

In order to realize an effective implosion, beam illumination non-uniformity on a fuel target must be suppressed less than a few percent. In this study, a direct–indirect mixture implosion mode is proposed and discussed in heavy ion beam (HIB) inertial confinement fusion (HIF) in order to release sufficient fusion energy in a robust manner. On the other hand, the HIB illumination non-uniformity depends strongly on a target displacement dz from the center of a fusion reactor chamber. In a direct-driven implosion mode, dz of ∼20 μm was tolerable, and in an indirect-implosion mode, dz of ∼100 μm was allowable. In the direct–indirect mixture mode target, a low-density foam layer is inserted, and the radiation energy is confined in the foam layer. In the foam layer, the radiation transport is expected to smooth the HIB illumination non-uniformity in the lateral direction. Two-dimensional implosion simulations are performed, and show that the HIB illumination non-uniformity is well smoothed in the direct–indirect mixture target. Our simulation results present that a large pellet displacement of approximately a few hundred microns is allowed in order to obtain a sufficient fusion energy output in HIF.

In this paper, significant progresses of Japanese research activities are presented in heavy ion fusion (HIF) and high energy density physics (HEDP). Heavy ion beam (HIB) is a prominent tool to study HEDP and HIF, and HIBs may be a promising inertial fusion driver. HIB accelerators have been studied intensively for a long time; HIB pulse profile, a particle energy and a HIB quality are controllable. A HIB energy deposition profile is also well defined, and HIB energy is deposited inside a material. By focusing and using the HIB excellent properties, Japanese HIF and HEDP activities have covered a wide variety of subjects ranging from new accelerators to future HIF studies: ion source, new inductive accelerator, beam physics, beam bunching, beam instabilities, HIB interactions with gas or materials, laser ion acceleration, HIB transport, HIB-based warm dense (WD) state generation, new measurement of HED or WD matters, HIB stopping power, atomic physics, multi-HIBs illumination on a target, HIF target implosion, impact ignition scheme, HIB-radiation conversion, radiation confinement and transport in HED matter or in HIF, and so on.

Dynamics of high-current heavy-ion beams are studied during longitudinal bunch compression. Operation regions of particle beams are plotted on a tune depression–wave velocity diagram. Emittance growth due to the transverse focusing field error is investigated during the final beam bunching. The beam bunch is longitudinally compressed during the transport with the field error in continuous focusing (CF) or alternating gradient (AG) field lattices. Numerical calculation results show the difference of the emittance growth is only 2% between the cases with and without field error in the CF lattice. On the other hand, in the case of AG lattice with field error of 10%, the emittance growth of 2.4 times is estimated. The beam behaviors in the CF and AG lattice transport are discussed based on the numerical simulations.

In heavy ion beam (HIB) inertial confinement fusion (HIF), implosion asymmetry should be less than a few percent in order to compress a fuel sufficiently and release fusion energy effectively. It is known that the HIB illumination nonuniformity and implosion symmetry are sensitive to a little pellet displacement from a reactor chamber center. We present a new HIB illumination scheme which is robust against the displacement of a direct-driven fuel pellet in an HIF reactor chamber. In conventional HIB illumination schemes a pellet displacement of 25–100 μm was tolerable. The new robust HIB illumination scheme is examined by three-dimensional computer simulations. In the new HIB illumination scheme the tolerable pellet displacement is about 200–300 μm.

Plasmas at high density and/or high-temperature state are produced using pulse power devices. Dense, cylindrically evolving plasmas are produced using pulse- power-driven exploding discharges in water. Shock-heated, high-temperature plasmas are produced also in a compact pulse power device. In contrast to the pulse-powered plasmas, properly moderated high-power ion beams can make a well-defined plasma over a wider range of density–temperature space. Their advantages and attainable parameter region are comparatively discussed as a driver for making the high-energy-density states.

A suppression of transverse proton divergence by a localization of high-energy electron bunch generated by an interaction between an intense laser and a foil target is investigated in this paper. When an intense laser illuminates a foil target, electrons are accelerated longitudinally by the ponderomotive force and produce a strong magnetic field. The electrons are confined by the magnetic field and an electric field is generated locally. Protons are extracted and mainly accelerated longitudinally by the local electric field. Consequently, the transverse divergence of high-energy protons is successfully suppressed.

In a particle accelerator system for heavy ion inertial fusion, space-charge-dominated beam dynamics is investigated during a final beam bunching. While the space charge effect undertakes an important role for the beam dynamics in the regime, the beam instability induced by space charge oscillation may occur, depending on the particle distribution of the beam. Particle simulations present that the instability due to the strong space charge effect may not be serious for realistic particle distributions during the final beam bunching.

In this paper, we propose an electron acceleration by using an intense short pulse laser and a thin slab plasma separator. When an intense short pulse laser illuminates electrons in vacuum, the electrons are accelerated by the ponderomotive force at the front of laser pulse and the electrons accelerated loose their energies at the tail of laser pulse. This is one of serious problems in the ponderomotive electron acceleration. In order to suppress the energy loss, we propose an overdense plasma separator to extract the electrons before entering the deceleration region of laser pulse. In our electron acceleration mechanism, only the laser is reflected by the overdense plasma separator and the electrons pass through the plasma separator. Consequently, the electrons can obtain a net energy after the interaction with the laser pulse.

Three-dimensional computer simulations are performed for a heavy ion beam (HIB) irradiation onto a direct-driven spherical fuel pellet in heavy ion fusion (HIF). In addition, the non-uniformity growth due to a little pellet displacement from a reactor chamber center is investigated. The calculation results demonstrate that we can realize a rather low non-uniform energy deposition: for example, less than 2.0% even for a 32-beam irradiation system. Moreover, we developed the above simulation code for more common purposes in the research fields of medical treatment, material processing, indirect-driven HIF and so on.

Possible ion beam parameters are investigated for bunch compression in the TARN II storage ring which is under consideration for applications at RIKEN. A fast rotation scheme is carried out to generate a high-current beam within the ring after accumulating and cooling a low-current ion beam. Consistent with achievable magnetic rigidity and space-charge tune shift, possible beam parameters during the beam stacking in the ring are estimated analytically. Beam properties during the bunch compression are studied with coupled envelope equations that take into account space-charge and dispersive forces acting on the beam. More self-consistent particle-in-cell simulations are also carried out, and the results are compared with the envelope calculations.

Beam dynamics is investigated by multiparticle simulations during final beam bunching and final beam focusing in a driver system for heavy-ion inertial fusion. The particle simulations predict the emittance growth during the longitudinal bunch compression for various particle distributions at initial conditions. Particle distributions in the beam transverse cross-section approach uniform during the final beam bunching. It is found that the distribution has the Gaussian profile at the focal spot in the radial direction after the final focusing.

For computer simulations on heavy ion beam (HIB) irradiation on a spherical fuel pellet in heavy ion fusion (HIF) the code OK1 was developed and presented in [Comput. Phys. Commun. 157 (2004) 160–172]. The new code OK2 is a modified upgraded computer program for more common purposes in research fields of medical treatment, material processing as well as HIF. OK2 provides computational capabilities of a three-dimensional ion beam energy deposition on a target with an arbitrary shape and structure. Program summary Title of program: OK2 Catalogue identifier: ADTZ Other versions of this program [1]: Title of the program: OK1 Catalogue identifier: ADST Program summary URL: http://cpc.cs.qub.as.uk/summaries/ADTZ Program obtainable from: CPC Program Library, Queen's University of Belfast, N. Ireland Computer: PC (Pentium 4, ∼1 GHz or more recommended) Operating system: Windows or UNIX Program language used: C++ Memory required to execute with typical data: 2048 MB No. of bits in a word: 32 No. of processors used: 1CPU Has the code been vectorized or parallelized: No No. of bytes in distributed program, including test data: 17 334 No of lines in distributed program, including test date: 1487 Distribution format: tar gzip file Nature of physical problem: In research areas of HIF (Heavy Ion Beam Inertial Fusion) energy [1–4] and medical material sciences [5], ion energy deposition profiles need to be evaluated and calculated precisely. Due to a favorable energy deposition behavior of ions in matter [1–4] it is expected that ion beams would be one of preferable candidates in various fields including HIF and material processing. Especially in HIF for a successful fuel ignition and a sufficient fusion energy release, a stringent requirement is imposed on the HIB irradiation non-uniformity, which should be less than a few percent [4,6,7]. In order to meet this requirement we need to evaluate the uniformity of a realistic HIB irradiation and energy deposition pattern. The HIB irradiation and non-uniformity evaluations are sophisticated and difficult to calculate analytically. Based on our code one can numerically obtain a three-dimensional profile of energy deposition onto an arbitrary shape and structure target. Method of solution: OK2 code works on the base of OK1 [1–9]. The code simulates a multi-beam illumination on a target with arbitrary shape and structure, and obtains the 3D energy deposition profile. Restrictions on the complexity of the problem: None Typical running time: The execution time depends on the pellet mesh number and the number of beams in the simulated illumination as well as on the beam characteristics (beam radius on the pellet surface, beam subdivision, projectile particle energy and so on). In almost of the practical running tests performed, the typical running time for one beam deposition is about 40 s on a PC with a CPU of Pentium 4, 2.4 GHz. Unusual features of the program: None References: [1] A.I. Ogoyski, et al., Code OK1—Simulation of multi-beam irradiation on a spherical target in heavy ion fusion, Comput. Phys. Commun. 157 (2004) 160–172. [2] J.J. Barnard, et al., Lawrence Livermore National Laboratory Research Report, UCRL-LR-108095 (1991). [3] C. Deutsch, et al., J. Plasma and Fusion Res. 77 (2001) 33. [4] T. Someya, et al., Fusion Science Tech. 43 (2003) 282–289. [5] S.V. Bulanov, et al., Phys. Lett. A 299 (2002) 240–247. [6] M.H. Emery, et al., Phys. Rev. Lett. 48 (1982) 253. [7] S. Kawata, et al., J. Phys. Soc. Japan 53 (1984) 3416. [8] T. Mehlhorn, Sandia Report, SAND80-0038 (1980). [9] H.H. Andersen, J.F. Ziegler, The Stopping and Ranges of Ions in Matter, vol. 3, Pergamon Press, Elmsford, NY, 1977.

Code OK1 is a fast and precise three-dimensional computer program designed for simulations of heavy ion beam (HIB) irradiation on a direct-driven spherical fuel pellet in heavy ion fusion (HIF). OK1 provides computational capabilities of a three-dimensional energy deposition profile on a spherical fuel pellet and the HIB irradiation non-uniformity evaluation, which are valuables for optimizations of the beam parameters and the fuel pellet structure, as well for further HIF experiment design. The code is open and complete, and can be easily modified or adapted for users' purposes in this field. Program summary Title of program: OK1 Catalogue identifier: ADST Program summary URL: http://cpc.cs.qub.ac.uk/summaries/ADST Program obtainable from: CPC Program Library, Queen's University of Belfast, N. Ireland Computer: PC (Pentium 4, ∼1 GHz or more recommended) Operating system: Windows or UNIX Program language used: C++ Memory required to execute with typical data: 911 MB No. of bits in a word: 32 No. of processors used: 1 CPU Has the code been vectorized or parallelized: No No. of bytes in distributed program, including test data: 16 557 Distribution format: tar gzip file Keywords: Heavy ion beam, inertial confinement fusion, energy deposition, fuel pellet Nature of physical problem: Nuclear fusion energy may have attractive features as one of our human energy resources. In this paper we focus on heavy ion inertial confinement fusion (HIF). Due to a favorable energy deposition behavior of heavy ions in matter [J.J. Barnard et al., UCRL-LR-108095, 1991; C. Deutsch et al., J. Plasma Fusion Res. 77 (2001) 33; T. Someya et al., Fusion Sci. Tech. (2003), submitted] it is expected that heavy ion beam (HIB) would be one of energy driver candidates to operate a future inertial confinement fusion power plant. For a successful fuel ignition and fusion energy release, a stringent requirement is imposed on the HIB irradiation non-uniformity, which should be less than a few percent [T. Someya et al., Fusion Sci. Tech. (2003), submitted; M.H. Emery et al., Phys. Rev. Lett. 48 (1982) 253; S. Kawata et al., J. Phys. Soc. Jpn. 53 (1984) 3416]. In order to meet this requirement we need to evaluate the non-uniformity of a realistic HIB irradiation and energy deposition pattern. The HIB irradiation and non-uniformity evaluations are sophisticated and difficult to calculate analytically. Based on our code one can numerically obtain a three-dimensional profile of energy deposition and evaluate the HIB irradiation non-uniformity onto a spherical target for a specific HIB parameter value set in HIF. Method of solution: OK1 code is based on the stopping power of ions in matter [J.J. Barnard et al., UCRL-LR-108095, 1991; C. Deutsch et al., J. Plasma Fusion Res. 77 (2001) 33; T. Someya et al., Fusion Sci. Tech. (2003), submitted; M.H. Emery et al., Phys. Rev. Lett. 48 (1982) 253; S. Kawata et al., J. Phys. Soc. Jpn. 53 (1984) 3416; T. Mehlhorn, SAND80-0038, 1980; H.H. Andersen, J.F. Ziegler, Pergamon Press, 1977, p. 3]. The code simulates a multi-beam irradiation, obtains the 3D energy deposition profile of the fuel pellet and evaluates the deposition non-uniformity. Restrictions on the complexity of the problem: No Typical running time: The execution time depends on the number of beams in the simulated irradiation and its characteristics (beam radius on the pellet surface, beam subdivision, projectile particle energy and so on). In almost of the practical running tests performed, the typical running time for one beam deposition is less than 2 s on a PC with a CPU of Pentium 4, 2.2 GHz (e.g., in Test 2 when the number of beams is 600, the running time is about 18 minutes). Unusual features of the program: No

A non-uniformity of heavy ion beam irradiation onto a direct-driven fuel pellet in heavy ion fusion (HIF) is studied numerically. The energy deposition non-uniformity is investigated by several beam irradiation systems. The results demonstrate for the first time in HIF that the deposition non-uniformity can be reduced to low values, for example, less than 2% for a 32-beam irradiation system.

In this paper we present a new transport scheme for an intense electron beam and for an intense ion beam using an insulator guide: charged particle extraction from a plasma generated at the insulator surface is self-regulated by the net space charge of the beam in order for effective charge neutralization. A part of the beam particles hits the insulator surface, and the particle charge accumulated at the insulator surface creates local discharges. The discharges produce the plasma at the insulator surface. In this paper we present particle-in-cell simulation results for the particle beam transport through the insulator guide. The simulation results demonstrate that the self-regulated space-charge neutralization is effectively achieved, and that the simplicity of the proposed scheme may increase its viability.

This paper shows that a 20% initial mixing inhomogeneity of deuterium (D) and tritium (T) fuels and also a 30% T reduction in a D-T pellet still give a sufficient fusion energy output in D-T inertial confinement fusion (ICF). One and two dimensional numerical simulations and estimation studies support these results. The results mean that fusion energy output and burn process are rather insensitive to the significant T reduction and to the initial inhomogeneous fuel mixing in the D-T ICF pellet.

This paper shows a new method for two-dimensional grid generation with orthogonality and uniformity of the line-spacing changing ratio. The grid generation method is based on the Poisson equations with orthogonality control functions and dynamically determined line-spacing control functions. The values of line-spacing control functions are determined in an iteration procedure in order to realize a uniform grid-size changing ratio specified by users. The method proposed is successfully applied to generations of two-dimensional grids in an O-type domain and a domain with three sides parallel to the Cartesian coordinates.

For computer simulations on heavy ion beam (HIB) irradiation onto a target with an arbitrary shape and structure in heavy ion fusion (HIF), the code OK2 was developed and presented in Computer Physics Communications 161 (2004). Code OK3 is an upgrade of OK2 including an important capability of wobbling beam illumination. The wobbling beam introduces a unique possibility for a smooth mechanism of inertial fusion target implosion, so that sufficient fusion energy is released to construct a fusion reactor in future. New version program summary Program title: OK3 Catalogue identifier: ADST_v3_0 Program summary URL: http://cpc.cs.qub.ac.uk/summaries/ADST_v3_0.html Program obtainable from: CPC Program Library, Queen's University, Belfast, N. Ireland Licensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.html No. of lines in distributed program, including test data, etc.: 221 517 No. of bytes in distributed program, including test data, etc.: 2 471 015 Distribution format: tar.gz Programming language: C++ Computer: PC (Pentium 4, 1 GHz or more recommended) Operating system: Windows or UNIX RAM: 2048 MBytes Classification: 19.7 Catalogue identifier of previous version: ADST_v2_0 Journal reference of previous version: Comput. Phys. Comm. 161 (2004) 143 Does the new version supersede the previous version?: Yes Nature of problem: In heavy ion fusion (HIF), ion cancer therapy, material processing, etc., a precise beam energy deposition is essentially important [1]. Codes OK1 and OK2 have been developed to simulate the heavy ion beam energy deposition in three-dimensional arbitrary shaped targets [2, 3]. Wobbling beam illumination is important to smooth the beam energy deposition nonuniformity in HIF, so that a uniform target implosion is realized and a sufficient fusion output energy is released. Solution method: OK3 code works on the base of OK1 and OK2 [2, 3]. The code simulates a multi-beam illumination on a target with arbitrary shape and structure, including beam wobbling function. Reasons for new version: The code OK3 is based on OK2 [3] and uses the same algorithm with some improvements, the most important one is the beam wobbling function. Summary of revisions: 1. In the code OK3, beams are subdivided on many bunches. The displacement of each bunch center from the initial beam direction is calculated. 2. Code OK3 allows the beamlet number to vary from bunch to bunch. That reduces the calculation error especially in case of very complicated mesh structure with big internal holes. 3. The target temperature rises during the time of energy deposition. 4. Some procedures are improved to perform faster. 5. The energy conservation is checked up on each step of calculation process and corrected if necessary. New procedures included in OK3 1. Procedure BeamCenterRot( ) rotates the beam axis around the impinging direction of each beam. 2. Procedure BeamletRot( ) rotates the beamlet axes that belong to each beam. 3. Procedure Rotation( ) sets the coordinates of rotated beams and beamlets in chamber and pellet systems. 4. Procedure BeamletOut( ) calculates the lost energy of ions that have not impinged on the target. 5. Procedure TargetT( ) sets the temperature of the target layer of energy deposition during the irradiation process. 6. Procedure ECL( ) checks up the energy conservation law at each step of the energy deposition process. 7. Procedure ECLt( ) performs the final check up of the energy conservation law at the end of deposition process. Modified procedures in OK3 1. Procedure InitBeam( ): This procedure initializes the beam radius and coefficients A1, A2, A3, A4 and A5 for Gauss distributed beams [2]. It is enlarged in OK3 and can set beams with radii from 1 to 20 mm. 2. Procedure kBunch( ) is modified to allow beamlet number variation from bunch to bunch during the deposition. 3. Procedure ijkSp( ) and procedure Hole( ) are modified to perform faster. 4. Procedure Espl( ) and procedure ChechE( ) are modified to increase the calculation accuracy. 5. Procedure SD( ) calculates the total relative root-mean-square (RMS) deviation and the total relative peak-to-valley (PTV) deviation in energy deposition non-uniformity. This procedure is not included in code OK2 because of its limited applications (for spherical targets only). It is taken from code OK1 and modified to perform with code OK3. Running time: The execution time depends on the pellet mesh number and the number of beams in the simulated illumination as well as on the beam characteristics (beam radius on the pellet surface, beam subdivision, projectile particle energy and so on). In almost all of the practical running tests performed, the typical running time for one beam deposition is about 30 s on a PC with a CPU of Pentium 4, 2.4 GHz. References: [1] A.I. Ogoyski, et al., Heavy ion beam irradiation non-uniformity in inertial fusion, Phys. Lett. A 315 (2003) 372–377. [2] A.I. Ogoyski, et al., Code OK1 – Simulation of multi-beam irradiation on a spherical target in heavy ion fusion, Comput. Phys. Comm. 157 (2004) 160–172. [3] A.I. Ogoyski, et al., Code OK2 – A simulation code of ion-beam illumination on an arbitrary shape and structure target, Comput. Phys. Comm. 161 (2004) 143–150.

The T cell line specific for a bacterial cell wall peptidoglycan subunit, disaccharide tetrapeptide of diaminopimelic acid type, was examined for epitope specificity in elicitation of delayed-type hypersensitivity (DTH) in X-irradiated Lewis rats, using pairs of analogs different in optical configuration of the COOH-terminal amino acid. The test cell line induced DTH against analogs with the COOH-terminal d -amino acid but not against those with the l -amino acid at the COOH terminus. A close correlation was found between the T cell line-induced DTH reaction in vivo and the proliferative response in vitro , in terms of clear discrimination of the optical configuration of COOH-terminal amino acid of disaccharide tetrapeptide. The l -isomers (non-stimulatory analogs of T cell proliferation) competitively inhibited the proliferation of the T cell line by the corresponding d -isomers. Thus the l -isomers appear to interact with Ia molecules on antigen-presenting cells. We conclude that COOH-terminal d -amino acid of the disaccharide tetrapeptide could be involved in binding to the T cell receptor, induction of T cell proliferation, and elicitation of DTH.